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Title: Recent results from the DIII-D tokamak and implications for future devices

Abstract

Improvements to the DIII-D tokamak have led to significant new research results and enhanced performance. These results provide important inputs to the design of next generation divertor systems including the upgrade of the DIII-D divertor. The use of graphite for the plasma facing components and careful wall preparation has enabled the routine achievement of regimes of enhanced energy confinement. In elongated discharges, triangularity has been found to be important in attaining good discharge performance as measured by the product of the normalized plasma pressure and the energy confinement time, {beta}{tau}{sub E} This constrains the design of the divertor configuration (X-point location). Active pumping of the divertor region using an in-situ toroidal cryogenic pump has demonstrated control of the plasma density in H-mode discharges and allowed the dependence of confinement on plasma density and current to be separately determined. Helium removal from the plasma edge sufficient to achieve effective ash removal in reactor discharges has also been demonstrated using this pumping configuration. The reduction of the heat flux to the divertor plates has been demonstrated using two different techniques to increase the radiation in the boundary regions of the plasma and thus reduce the heat flux to the divertor plates; deuteriummore » gas injection has been used to create a strongly radiating localized zone near the X-point, and impurity (neon) injection to enhance the radiation from the plasma mantle. Precise shaping of the plasma current profile has been found to be important in achieving enhanced tokamak performance. Transiently shaped current profiles have been used to demonstrate regimes of plasmas with high beta and good confinement. Control of the current profile also is important to sustaining the plasma in the Very High (VH)-mode of energy confinement.« less

Authors:
 [1]
  1. General Atomics, San Diego, CA (United States)
Publication Date:
Research Org.:
General Atomics, San Diego, CA (United States); Oak Ridge National Lab., TN (United States); Lawrence Livermore National Lab., CA (United States); Sandia National Labs., Albuquerque, NM (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
46710
Report Number(s):
GA-A-21814; CONF-940843-18
ON: DE95009605; TRN: 95:010994
DOE Contract Number:  
AC03-89ER51114; AC05-84OR21400; W-7405-ENG-48; AC04-76DP00789
Resource Type:
Conference
Resource Relation:
Conference: 18. European symposium on fusion technology (SOFT-18), Karlsruhe (Germany), 22-26 Aug 1994; Other Information: PBD: Feb 1995
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION; DOUBLET-3 DEVICE; RESEARCH PROGRAMS; TOKAMAK DEVICES; DESIGN; PERFORMANCE; OPERATION; THERMONUCLEAR REACTOR MATERIALS; HELIUM ASH; PLASMA IMPURITIES; ICR HEATING; MICROWAVE EQUIPMENT; VACUUM SYSTEMS

Citation Formats

Luxon, J L. Recent results from the DIII-D tokamak and implications for future devices. United States: N. p., 1995. Web.
Luxon, J L. Recent results from the DIII-D tokamak and implications for future devices. United States.
Luxon, J L. Wed . "Recent results from the DIII-D tokamak and implications for future devices". United States. https://www.osti.gov/servlets/purl/46710.
@article{osti_46710,
title = {Recent results from the DIII-D tokamak and implications for future devices},
author = {Luxon, J L},
abstractNote = {Improvements to the DIII-D tokamak have led to significant new research results and enhanced performance. These results provide important inputs to the design of next generation divertor systems including the upgrade of the DIII-D divertor. The use of graphite for the plasma facing components and careful wall preparation has enabled the routine achievement of regimes of enhanced energy confinement. In elongated discharges, triangularity has been found to be important in attaining good discharge performance as measured by the product of the normalized plasma pressure and the energy confinement time, {beta}{tau}{sub E} This constrains the design of the divertor configuration (X-point location). Active pumping of the divertor region using an in-situ toroidal cryogenic pump has demonstrated control of the plasma density in H-mode discharges and allowed the dependence of confinement on plasma density and current to be separately determined. Helium removal from the plasma edge sufficient to achieve effective ash removal in reactor discharges has also been demonstrated using this pumping configuration. The reduction of the heat flux to the divertor plates has been demonstrated using two different techniques to increase the radiation in the boundary regions of the plasma and thus reduce the heat flux to the divertor plates; deuterium gas injection has been used to create a strongly radiating localized zone near the X-point, and impurity (neon) injection to enhance the radiation from the plasma mantle. Precise shaping of the plasma current profile has been found to be important in achieving enhanced tokamak performance. Transiently shaped current profiles have been used to demonstrate regimes of plasmas with high beta and good confinement. Control of the current profile also is important to sustaining the plasma in the Very High (VH)-mode of energy confinement.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1995},
month = {2}
}

Conference:
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